Peculiarity of deuterium ions interaction with tungsten surface in the condition imitating combination of normal operation with plasma disruption in ITER
- 15 March 2001
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 290-293, 1069-1073
- https://doi.org/10.1016/s0022-3115(00)00471-2
Abstract
No abstract availableKeywords
This publication has 12 references indexed in Scilit:
- Assessment of tungsten for use in the ITER plasma facing componentsPublished by Elsevier ,2002
- Behavior of plasma-sprayed tungsten coatings on CFC and graphite under high heat loadJournal of Nuclear Materials, 1999
- Growth of redeposited carbon and its impact on isotope retention properties on tungsten in a high flux deuterium plasmaJournal of Nuclear Materials, 1999
- Conclusions about the use of tungsten in the divertor of ASDEX UpgradeJournal of Nuclear Materials, 1999
- The effect of ion damage on deuterium trapping in tungstenJournal of Nuclear Materials, 1999
- Tritium retention in tungsten exposed to intense fluxes of 100 eV tritonsJournal of Nuclear Materials, 1999
- In-vessel tritium retention and removal in ITERJournal of Nuclear Materials, 1999
- Retention and release of deuterium implanted in W and MoJournal of Nuclear Materials, 1999
- Deuterium retention in tungsten for fusion useJournal of Nuclear Materials, 1998
- Erosion of carbon-based materials in a steady-state deuterium plasmaJournal of Nuclear Materials, 1998